Experimental study of Siphon breaker about size effect in real scale reactor design

Conference · Sun Jul 01 00:00:00 EDT 2012

OSTI ID:22106058

Kang, S. H. ^[1]; Ahn, H. S. ^[2]; Kim, J. M. ^[1]; Joo, H. M. ^[3]; Lee, K. Y.; Seo, K.; Chi, D. Y. ^[4]; Kim, M. H. ^[2]

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1. Mechanical Engineering Dept., POSTECH, Pohang, 790-784 (Korea, Republic of)
2. Div. of Advanced Nuclear Engineering, POSTECH, Pohang, 790-784 (Korea, Republic of)
3. Dept. of Nuclear Engineering, Hanyang Univ., Seoul, 133-791 (Korea, Republic of)
4. KAERI, Yuseong, Daejeon, 305-353 (Korea, Republic of)

Rupture accident within the pipe of a nuclear reactor is one of the main causes of a loss of coolant accident (LOCA). Siphon-breaking is a passive method that can prevent a LOCA. In this study, either a line or a hole is used as a siphon-breaker, and the effect of various parameters, such as the siphon-breaker size, pipe rupture point, pipe rupture size, and the presence of an orifice, are investigated using an experimental facility similar in size to a full-scale reactor. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 22106058
• Resource Relation: Conference: ICAPP '12: 2012 International Congress on Advances in Nuclear Power Plants, Chicago, IL (United States), 24-28 Jun 2012; Other Information: Country of input: France; 4 refs.; Related Information: In: Proceedings of the 2012 International Congress on Advances in Nuclear Power Plants - ICAPP '12| 2799 p.
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
EXPERIMENTAL DATA
LOSS OF COOLANT
NUCLEAR POWER PLANTS
ORIFICES
RUPTURES